TRAC-PF1/MOD2 status and plans
The development of the TRAC-PF1/MOD1 code was completed in July 1988 with the release of Version 14.4. A TRAC-PF1/MOD2 code development plan addresses code deficiencies identified in the MOD1 code in order to provide an accurate and defensible tool that can be used to simulate large-break loss-of-coolant accidents (LOCAs), small-break LOCAs, and operational transients. The MOD2 code development plan is an international cooperative effort that includes contributions from Los Alamos National Laboratory, Idaho National Engineering Laboratory (INEL), Japanese Atomic Energy Research Institute (JAERI), Cray Research, Central Electricity Generating Board (CEGB), and United Kingdom Atomic Energy Authority (UKAEA). 8 refs., 7 figs.
- Research Organization:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 6953471
- Report Number(s):
- LA-UR-88-3846; CONF-8810155-20; ON: DE89003494
- Resource Relation:
- Conference: 16. water reactor safety information meeting, Gaithersburg, MD, USA, 24 Oct 1988; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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TRAC-PF1/MOD2 best-estimate analysis of a large-break LOCA in a 15 {times} 15 generic four-loop Westinghouse nuclear power plant
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Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
REACTOR ACCIDENTS
COMPUTERIZED SIMULATION
COMPUTER CALCULATIONS
HEAT TRANSFER
LOSS OF COOLANT
REACTOR SAFETY
T CODES
ACCIDENTS
COMPUTER CODES
ENERGY TRANSFER
SAFETY
SIMULATION
220900* - Nuclear Reactor Technology- Reactor Safety
990220 - Computers
Computerized Models
& Computer Programs- (1987-1989)